CHEMICAL TECHNOLOGY BRANCH ANNUAL REPORT, FISCAL YEAR 1969.
- ed.
- Research Organization:
- Idaho Nuclear Corp., Idaho Falls
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-24-009429
- OSTI ID:
- 4735617
- Report Number(s):
- IN--1314
- Country of Publication:
- United States
- Language:
- English
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ALUMINUM ALLOYS AND SYSTEMS/Al- -U
dissolution of fuels of
ALUMINUM ALLOYS-- CENTRIFUGATION-- DESIGN-- FISSION PRODUCTS-- NEPTUNIUM-- PLUTONIUM-- SAFETY-- URANIUM-- URANIUM ALLOYS
CHEMICAL REACTIONS-- DENITRATION-- NITRIC ACID-- PRODUCTION-- URANIUM TRIOXIDE-- URANYL NITRATES
CHEMICAL REACTIONS-- SAFETY
COMBUSTION-- GRAPHITE-- LEACHING-- SOLVENT EXTRACTION
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FISSION PRODUCTS/separation from neptunium
FLUIDIZATION
FLUIDIZED BED
FUELS
N20510* --Chemistry--Radiochemistry &
N20540 --Chemistry--Radiochemistry &
NEPTUNIUM/separation from spent fuels
Nuclear Chemistry-- Reactor Fuel Processing
Nuclear Chemistry--Radioactive Waste Treatment
PERFORMANCE
PLUTONIUM/separation from nep
RADIOACTIVE WASTE/calcination of
use of in-bed combustion of fuel for heating fluidized-bed calciner for
RADIOACTIVE WASTE/management of
studies on
RADIOACTIVE WASTE/storage of solid calcined
RADIOCHEMICAL PROCESSING PLANTS/design and safety analysis of
for fluidized-bed denitration of uranyl nitrate
REACTOR FUELS/ dissolution of EBR-II
electrolytic
REACTOR FUELS/reprocessing of graphite
fluidized-bed combustion methods in
REPROCESSING
SEPARATION PROCESSES CALCINATION-- CONTROL-- HEATING-- PYROLYSIS-- RADIOACTIVE WASTES-- STORAGE-- WASTE PROCESSING
URANIUM ALLOYS AND SYSTEMS/Al--U
dissolution of fuels of
URANIUM OXIDES UO$sub 3$/production by denitration of uranyl nitrate
design and safety analysis of fluidized-bed facility for
URANIUM/Separation from spent graphite fuels by combined combustion, leaching, and solvent extraction process
URANYL NITRATES/ denitration of
design and safety analysis of fluidized-bed facility for
dissolution of fuels of
ALUMINUM ALLOYS-- CENTRIFUGATION-- DESIGN-- FISSION PRODUCTS-- NEPTUNIUM-- PLUTONIUM-- SAFETY-- URANIUM-- URANIUM ALLOYS
CHEMICAL REACTIONS-- DENITRATION-- NITRIC ACID-- PRODUCTION-- URANIUM TRIOXIDE-- URANYL NITRATES
CHEMICAL REACTIONS-- SAFETY
COMBUSTION-- GRAPHITE-- LEACHING-- SOLVENT EXTRACTION
EBR-2-- ELECTROLYSIS-- RESEARCH REACTORS-- SOLUBILITY
FISSION PRODUCTS/separation from neptunium
FLUIDIZATION
FLUIDIZED BED
FUELS
N20510* --Chemistry--Radiochemistry &
N20540 --Chemistry--Radiochemistry &
NEPTUNIUM/separation from spent fuels
Nuclear Chemistry-- Reactor Fuel Processing
Nuclear Chemistry--Radioactive Waste Treatment
PERFORMANCE
PLUTONIUM/separation from nep
RADIOACTIVE WASTE/calcination of
use of in-bed combustion of fuel for heating fluidized-bed calciner for
RADIOACTIVE WASTE/management of
studies on
RADIOACTIVE WASTE/storage of solid calcined
RADIOCHEMICAL PROCESSING PLANTS/design and safety analysis of
for fluidized-bed denitration of uranyl nitrate
REACTOR FUELS/ dissolution of EBR-II
electrolytic
REACTOR FUELS/reprocessing of graphite
fluidized-bed combustion methods in
REPROCESSING
SEPARATION PROCESSES CALCINATION-- CONTROL-- HEATING-- PYROLYSIS-- RADIOACTIVE WASTES-- STORAGE-- WASTE PROCESSING
URANIUM ALLOYS AND SYSTEMS/Al--U
dissolution of fuels of
URANIUM OXIDES UO$sub 3$/production by denitration of uranyl nitrate
design and safety analysis of fluidized-bed facility for
URANIUM/Separation from spent graphite fuels by combined combustion, leaching, and solvent extraction process
URANYL NITRATES/ denitration of
design and safety analysis of fluidized-bed facility for